Tài liệu miễn phí Năng lượng
Download Tài liệu học tập miễn phí Năng lượng
a-decay half-lives of some nuclei from ground state to ground state using different nuclear potential
Theoretical a-decay half-lives of some nuclei from ground state to ground state are calculated using different nuclear potential model including Coulomb proximity potential (CPPM), Royer proximity potential and Broglia and Winther 1991. The calculated values comparing with experimental data, it is observed that the CPPM model is in good agreement with the experimental data.
6/18/2020 5:41:58 AM +00:00
The characterization of radioactive waste: a critical review of techniques implemented or under development at CEA, France
This review paper describes the destructive and non-destructive measurements implemented or under development at CEA, in view to perform the most complete radioactive waste characterization.
6/18/2020 5:41:50 AM +00:00
CESAR5.3: Isotopic depletion for Research and Testing Reactor decommissioning
The aim of this paper is to describe how CESAR operates and how it can be used to help these facilities care for waste disposal, nuclear materials transport or basic safety cases. The test case will be based on the PHEBUS Facility located at CEA Cadarache.
6/18/2020 5:41:44 AM +00:00
An optimization methodology for heterogeneous minor actinides transmutation
In this paper, a simplified methodology for the design of targets is coupled with a method for the optimization of transmutation which takes into account both transmutation performances and fuel cycle impacts. The uncertainties and performances of this methodology are evaluated and shown to be sufficient to carry out scoping studies.
6/18/2020 5:41:38 AM +00:00
Beam dynamics and electromagnetic studies of a 3 MeV, 325 MHz radio frequency quadrupole accelerator
We present the beam dynamics and electromagnetic studies of a 3 MeV, 325 MHz H radio frequency quadrupole (RFQ) accelerator for the proposed Indian Spallation Neutron Source project. We have followed a design approach, where the emittance growth and the losses are minimized by keeping the tune depression ratio larger than 0.5.
6/18/2020 5:41:31 AM +00:00
Reflector features and physics consideration issued from the Jules Horowitz Reactor design analyses
Mechanic solicitations induced by neutron and photon interactions have to be featured for components lifespan determination. TechnicAtome is in charge of both the design and building on behalf of CEA of the 100 MW Jules Horowitz Reactor (JHR). This modular Material Testing Reactor is under construction in southern France, with radioisotope production and material testing capabilities.
6/18/2020 5:41:24 AM +00:00
A multi-physics analysis for the actuation of the SSS in Opal reactor
OPAL is a 20 MWth multi-purpose open-pool type Research Reactor located at Lucas Heights, Australia. It was designed, built and commissioned by INVAP between 2000 and 2006 and it has been operated by the Australia Nuclear Science and Technology Organization (ANSTO) showing a very good overall performance.
6/18/2020 5:41:18 AM +00:00
Single Event Effect cross section calibration and application to quasi-monoenergetic and spallation facilities
We describe an approach to calibrate Single Event Effect (SEE)-based detectors in monoenergetic fields and apply the resulting semi-empiric responses to more general mixed-field cases in which a broad variety of particle species and energy spectra are present.
6/18/2020 5:41:12 AM +00:00
A method for phenomenological and chemical kinetics study of autocatalytic reactive dissolution by optical microscopy. The case of uranium dioxide dissolution in nitric acid media
This study aims at better understanding the chemical and physico-chemical phenomena of uranium dioxide dissolution reactions in nitric acid media in the Purex process, which separates the reusable materials and the final wastes of the spent nuclear fuels.
6/18/2020 5:41:05 AM +00:00
Effects of the initial granular structure of clay sealing materials on their swelling properties: experiments and DEM simulations
The present study focuses on the material behaviour before homogenisation. A grain-scale experimental characterisation is first performed in the laboratory.
6/18/2020 5:26:17 AM +00:00
Hydraulic and statistical study of metastable phenomena in PWR rod bundles
The present work aims at improving our understanding of nefarious reorganisation phenomena observed by numerous studies in the flow large-scale structures. 3D simulations allowed identifying two distinct reorganisations consisting in a sign change for either a transverse velocity in rod-to-rod gaps or for a subchannel vortex.
6/18/2020 5:26:11 AM +00:00
Contribution to the study of fission products release from nuclear fuels in severe accident conditions: effect of the pO2 on Cs, Mo and Ba speciation
The objective of this work is to experimentally investigate the effect of the oxygen potential on the fuel and FP chemical behaviour in conditions representative of a severe accident. More specifically, the speciation of Cs, Mo and Ba is investigated.
6/18/2020 5:26:05 AM +00:00
Modeling and control of xenon oscillations in thermal neutron reactors
We study axial core oscillations due to xenon poisoning in thermal neutron nuclear reactors with simple 1D models: a linear one-group model, a linear two-group model, and a non-linear model taking the Doppler effect into account.
6/18/2020 5:25:59 AM +00:00
Analysis of radionuclides in microsystem: application to the selective recovery of 55Fe by solvent extraction
This study already demonstrate the high potential of microfluidic technology to improve analytical operations on D&D samples. This method will further be validated with radioactive samples.
6/18/2020 5:25:53 AM +00:00
Use case 3: post accidental site remediation CEA
This paper is dedicated to the sampling strategy for use case 3 (UC3) about contaminated soils, in the context of post-incidental remediation of a site. For this use case, the constraint environment comes from the difficulty to collect samples beneath a building on the one hand and the fact that samples were collected in the past with no possibility for additional samples.
6/18/2020 5:25:47 AM +00:00
Development of a user-friendly guideline for data analysis and sampling design strategy
Within the H2020 INSIDER project, the main objective of work package 3 (WP3) is to draft a sampling guide for initial nuclear site characterization in constraint environments, before decommissioning, based on a statistical approach.
6/18/2020 5:25:41 AM +00:00
SESAME project: advancements in liquid metal thermal hydraulics experiments and simulations
This paper will present the progress in the project with respect to liquid metal cooled reactor thermal-hydraulics (liquid metal heat transfer, fuel assembly thermal-hydraulics, pool thermal-hydraulics, and system thermal-hydraulics).
6/18/2020 5:25:35 AM +00:00
JRC in Euratom Research and Training Programme 2014–2020
The paper highlights some of the achievements of recent JRC direct actions with a focus on the interaction with EU MS research organisations, as well as some of the most important elements of the Commission Proposal for the next (2021–2025) Euratom Programme, with a focus on the new positioning of the JRC as regards its participation in indirect actions.
6/18/2020 5:25:29 AM +00:00
An improved method to evaluate the “Joint Oxyde-Gaine” formation in (U,Pu)O2 irradiated fuels using the GERMINAL V2 code coupled to Calphad thermodynamic computations
In this work, two different thermodynamic softwares, ANGE using the TBASE database, and OPENCALPHAD using the TAF-ID (Thermodynamics of Advanced Fuels – International Database), have been integrated into the GERMINAL V2 fuel performance code (of the PLEIADES platform) in order to evaluate the chemical state of (U,Pu)O2 fuel and fission products in sodium cooled fast reactors.
6/18/2020 5:25:23 AM +00:00
A nuclear owner/operator perspective on ways and means for joint programming on predisposal activities
Nuclear decommissioning is a worldwide competitive market. It is also the main source of radioactive waste from the nuclear energy field. In order to reduce the waste volume it is necessary to sort the actual radioactive waste to be disposed of and to separate them from other materials that could be recycled.
6/18/2020 5:25:17 AM +00:00
EURAD the European Joint Programme for research on radioactive waste management between EU members states national programmes
RD&D will continue to be necessary to develop, maintain and consolidate knowledge throughout the stepwise development, operation and closure of disposal facilities, which will be spread over many decades and make this knowledge available to all end users.
6/18/2020 5:25:11 AM +00:00
Needs of countries with longer timescale for deep geological repository implementation
In the paper the challenges and needs of a country with longer implementation timescale for DGR will be introduced through the example of Hungary.
6/18/2020 5:25:04 AM +00:00
Beacon: bentonite mechanical evolution
The aim of Beacon is to develop the understanding of fundamental processes that lead to material homogenisation, as well as to improve capabilities for numerical modelling. In earlier assessments of bentonite EBS, the mechanical interaction between the installed bentonite components has been neglected and an “ideal” final state has generally been assumed.
6/18/2020 5:24:58 AM +00:00
Science underpinning the safety case of deep geological repositories challenges in the past and in the future and how to maintain knowledge and competence during operation
Final repositories for spent nuclear fuel are approaching implementation. A prerequisite for these advancements is that it has been shown that the repository can be constructed and operated in practice in such a way that safety can be assured both during operation and over very long time scales.
6/18/2020 5:24:52 AM +00:00
Thermal treatment for radioactive waste minimisation
Safety case implications will also be assessed through the study of the disposability of thermally treated waste products. This paper will communicate the strategic aims of the ongoing project and highlight some key findings and results achieved to date.
6/18/2020 5:24:46 AM +00:00
Partitioning and transmutation contribution of MYRRHA to an EU strategy for HLW management and main achievements of MYRRHA related FP7 and H2020 projects: MYRTE, MARISA, MAXSIMA, SEARCH, MAX, FREYA, ARCAS
Today, nuclear power produces 11% of the world’s electricity. Nuclear power plants produce virtually no greenhouse gases or air pollutants during their operation. Emissions over their entire life cycle are very low.
6/18/2020 5:24:40 AM +00:00
INSIDER WP5 (in situ measurements): developed activities, main results and conclusions
An additional task is to organise the participation in in situ intercomparison exercises in real situations, defining the most suitable equipment to carry these out. This paper presents the activities of the WP5 and a summary of the main results obtained in these activities after the first two years of work.
6/18/2020 5:24:34 AM +00:00
Metrology applications to D&D issues: issues at stake for INSIDER European project
Nuclear metrology is an essential aspect to consider for further improvements of the initial characterization of sites under decommissioning. The H2020 Euratom project INSIDER in June 2017 aims at improving the management of contaminated materials arising from decommissioning and dismantling (D&D) operations by proposing an integrated methodology for radiological characterization.
6/18/2020 5:24:28 AM +00:00
Uncertainty propagation for the design study of the PETALE experimental programme in the CROCUS reactor
The PETALE experimental programme in the CROCUS reactor intends to provide integral measurements to constrain stainless steel nuclear data. This article presents the tools and the methodology developed to design and optimize the experiments, and its operating principle.
6/18/2020 5:24:20 AM +00:00
Uncertainty propagation based on correlated sampling technique for nuclear data applications
A correlated sampling technique has been implemented to estimate the impact of cross section modifications on the neutron transport and in Monte Carlo simulations in one single calculation. This implementation has been coupled to a Total Monte Carlo approach which consists in propagating nuclear data uncertainties with random cross section files.
6/18/2020 5:24:13 AM +00:00